Similar Documents at Cook |
---|
Category:Letter
MONTHYEARAEP-NRC-2024-79, Unit 2, Independent Spent Fuel Storage Installation - Registration of Dry Spent Storage Cask2024-09-26026 September 2024 Unit 2, Independent Spent Fuel Storage Installation - Registration of Dry Spent Storage Cask AEP-NRC-2024-78, Reply to a Notice of Violation: EA-24-0472024-09-23023 September 2024 Reply to a Notice of Violation: EA-24-047 05000316/LER-2024-002, Manual Reactor Trip Following Rapid Downpower for Steam Leak2024-09-12012 September 2024 Manual Reactor Trip Following Rapid Downpower for Steam Leak IR 05000315/20244022024-09-10010 September 2024 Security Baseline Inspection Report 05000315/2024402 and 05000316/2024402, Independent Spent Fuel Storage Installation Security Inspection Report 07200072/2024401 AEP-NRC-2024-69, Core Operating Limits Report2024-09-0909 September 2024 Core Operating Limits Report IR 05000315/20243012024-09-0505 September 2024 NRC Initial License Examination Report 05000315/2024301 and 05000316/2024301 ML24225A0022024-09-0303 September 2024 Issuance of Amendment Nos. 363 and 344 Revising Technical Specifications Section 3.8.1, AC Sources-Operating, for a One-Time Extension of a Completion Time IR 05000315/20240112024-08-30030 August 2024 NRC Inspection Report 05000315/2024011 and 05000316/2024011 and Notice of Violation AEP-NRC-2024-51, Annual Report of Loss-Of-Coolant Accident Evaluation Model Changes2024-08-28028 August 2024 Annual Report of Loss-Of-Coolant Accident Evaluation Model Changes AEP-NRC-2024-76, Unit 2 - Supplement to License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating2024-08-28028 August 2024 Unit 2 - Supplement to License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating 05000316/LER-2024-003, Plant Shutdown Required by Technical Specifications Due to Reactor Coolant System Identified Leakage2024-08-22022 August 2024 Plant Shutdown Required by Technical Specifications Due to Reactor Coolant System Identified Leakage IR 05000315/20240052024-08-21021 August 2024 Updated Inspection Plan for Donald C. Cook Nuclear Plant, Units 1 and 2 (Report 05000315/2024005 and 05000316/2024005) AEP-NRC-2024-61, Unit 2 - Response to Request for Additional Information for Neutron Flux Instrumentation License Amendment Request2024-08-15015 August 2024 Unit 2 - Response to Request for Additional Information for Neutron Flux Instrumentation License Amendment Request ML24221A2702024-08-0808 August 2024 Unit 2 Independent Spent Fuel Storage Installation - Registration of Dry Spent Fuel Storage Cask AEP-NRC-2024-62, Unit 2, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Cask2024-08-0707 August 2024 Unit 2, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Cask ML24256A1482024-08-0202 August 2024 2024 Post Examination Submittal Letter AEP-NRC-2024-47, Form OAR-1, Owners Activity Report2024-07-30030 July 2024 Form OAR-1, Owners Activity Report ML24169A2142024-07-25025 July 2024 Issuance of Amendment No. 362 Regarding Change to Technical Specification 3.4.12, Low Temperature Overpressure Protection System ML24183A0162024-07-25025 July 2024 Review of Reactor Vessel Material Surveillance Program Capsule W Technical Report IR 05000315/20240022024-07-24024 July 2024 Integrated Inspection Report 05000315/2024002 and 05000316/2024002 ML24197A1262024-07-15015 July 2024 Unit 2 - Request for Additional Information (RAI) for License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating AEP-NRC-2024-52, Manual Reactor Trip Following Rapid Downpower for Steam Leak2024-07-15015 July 2024 Manual Reactor Trip Following Rapid Downpower for Steam Leak ML24191A0692024-07-0909 July 2024 Operator Licensing Examination Approval - Donald C. Cook Nuclear Power Plant, July 2024 AEP-NRC-2024-56, Unit 2, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Cask2024-07-0808 July 2024 Unit 2, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Cask AEP-NRC-2024-48, Response to Request for Additional Information (RAI) for License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating2024-07-0202 July 2024 Response to Request for Additional Information (RAI) for License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating ML24176A1012024-06-21021 June 2024 57143-EN 57143 - Paragon Energy Solutions - Update 1 (Final) - 10CFR Part 21 Final Notification: P21-05242024-FN, Rev. 0 AEP-NRC-2024-45, Report Per Technical Specification 5.6.6 for Inoperability of Post Accident Monitoring Neutron Flux Monitoring2024-06-13013 June 2024 Report Per Technical Specification 5.6.6 for Inoperability of Post Accident Monitoring Neutron Flux Monitoring ML24163A0132024-06-12012 June 2024 Request for Information for the NRC Age-Related Degradation Inspection: Inspection Report 05000315/2024012 and 05000316/2024012 AEP-NRC-2024-23, Core Operating Limits Report2024-05-23023 May 2024 Core Operating Limits Report ML24141A2162024-05-20020 May 2024 —Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection AEP-NRC-2024-30, Reactor Trip Due to Main Turbine Trip from a High-High Thrust Bearing Position Trip2024-05-20020 May 2024 Reactor Trip Due to Main Turbine Trip from a High-High Thrust Bearing Position Trip AEP-NRC-2024-40, Unit 2 - Supplement to License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating2024-05-16016 May 2024 Unit 2 - Supplement to License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating AEP-NRC-2024-41, Annual Radiological Environmental Operating Report2024-05-15015 May 2024 Annual Radiological Environmental Operating Report IR 05000315/20240012024-05-14014 May 2024 Integrated Inspection Report 05000315/2024001 and 05000316/2024001 AEP-NRC-2024-07, Unit 2 - Transmittal of Report of Changes to the Emergency Plan2024-05-14014 May 2024 Unit 2 - Transmittal of Report of Changes to the Emergency Plan IR 05000315/20244012024-05-14014 May 2024 – Security Baseline Inspection Report 05000315/2024401 and 05000316/2024401 AEP-NRC-2024-26, Transmittal of Donald C. Cook Nuclear Plant, Emergency Plan Revision 492024-05-14014 May 2024 Transmittal of Donald C. Cook Nuclear Plant, Emergency Plan Revision 49 ML24115A2152024-05-0707 May 2024 LTR: CNP Non-Acceptance with Opportunity TS 3-8-1 AEP-NRC-2024-24, Form OAR-1, Owners Activity Report2024-05-0707 May 2024 Form OAR-1, Owners Activity Report ML24256A1472024-05-0606 May 2024 DC Cook 2024 NRC Examination Submittal Letter: Submittal ML24116A0002024-05-0202 May 2024 – Regulatory Audit in Support of Review of the Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors AEP-NRC-2024-35, Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations2024-04-30030 April 2024 Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations AEP-NRC-2024-28, 2023 Annual Radioactive Effluent Release Report2024-04-29029 April 2024 2023 Annual Radioactive Effluent Release Report AEP-NRC-2024-31, Annual Report of Individual Monitoring2024-04-24024 April 2024 Annual Report of Individual Monitoring AEP-NRC-2024-02, Unit 2 License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating2024-04-0303 April 2024 Unit 2 License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating AEP-NRC-2024-29, (CNP) Unit 2 - Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-072024-04-0303 April 2024 (CNP) Unit 2 - Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-07 AEP-NRC-2024-19, Annual Report of Property Insurance2024-04-0101 April 2024 Annual Report of Property Insurance AEP-NRC-2024-04, License Amendment Request Regarding a Change to Unit 1 Technical Specification 3.4.12, Low Temperature Overpressure Protection (LTOP) System2024-03-0606 March 2024 License Amendment Request Regarding a Change to Unit 1 Technical Specification 3.4.12, Low Temperature Overpressure Protection (LTOP) System ML24073A2342024-03-0606 March 2024 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors IR 05000315/20230062024-02-28028 February 2024 Annual Assessment Letter for Donald C. Cook Nuclear Plant, Units 1 and 2 (Report 05000315/2023006 and 05000316/2023006) 2024-09-09
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000316/LER-2024-002, Manual Reactor Trip Following Rapid Downpower for Steam Leak2024-09-12012 September 2024 Manual Reactor Trip Following Rapid Downpower for Steam Leak 05000316/LER-2024-003, Plant Shutdown Required by Technical Specifications Due to Reactor Coolant System Identified Leakage2024-08-22022 August 2024 Plant Shutdown Required by Technical Specifications Due to Reactor Coolant System Identified Leakage AEP-NRC-2024-52, Manual Reactor Trip Following Rapid Downpower for Steam Leak2024-07-15015 July 2024 Manual Reactor Trip Following Rapid Downpower for Steam Leak AEP-NRC-2024-30, Reactor Trip Due to Main Turbine Trip from a High-High Thrust Bearing Position Trip2024-05-20020 May 2024 Reactor Trip Due to Main Turbine Trip from a High-High Thrust Bearing Position Trip 05000316/LER-2017-0012017-05-19019 May 2017 1 OF 5, LER 17-001-00 for Cook, Unit 2 re Containment Hydrogen Skimmer Ventilation Fan #1 Inoperable Longer than Allowed by Technical Specifications 05000316/LER-2016-0022017-02-0909 February 2017 Emergency Diesel Generators Declared Inoperable Due to a Manufacturing Design Issue, LER 16-002-00 for Donald C. Cook Nuclear Plant Unit 2 Regarding Emergency Diesel Generators Declared Inoperable Due to a Manufacturing Design Issue 05000316/LER-2016-0012016-08-31031 August 2016 Manual Reactor Trip Due To Moisture Separator Heater Expansion Joint Failure, LER 16-001-00 for Donald C. Cook Nuclear Plant, Unit 2 Regarding Manual Reactor Trip Due To Moisture Separator Heater Expansion Joint Failure ML16193A3902016-07-15015 July 2016 Donald C. Cook Nuclear Plant Unit 2 - A Loss of Main Condenser Event Occurred Due to a Storm-Induced Debris Damage of the Circulating Water System Pumps in the Forebay (LER-316-2014-003-00) 05000315/LER-2015-0022016-01-18018 January 2016 -Technical Specification Violation due to Inoperable Residual. Heat Removal Pump, LER 15-002-01 for D.C. Cook, Unit 1, Regarding Technical Specification Violation Due to Inoperable Residual Heat Removal Pump 05000316/LER-2015-0012016-01-15015 January 2016 Manual Reactor Trip Due To A Secondary Plant Transient, LER 15-001-01 for D.C. Cook, Unit 2, Regarding Manual Reactor Trip Due to a Secondary Plant Transient ML0528703602005-10-0505 October 2005 Special Report for D. C. Cook Unit 2 Re Unit 2 Reactor Coolant Inventory Tracking System ML0508903452005-03-22022 March 2005 LER 99-001-01 Donald C. Cook Nuclear Plant Unit 2, Regarding Supplemental LER for Degraded Component Cooling Water Flow to Containment Main Steam Line Penetrations ML0210601432002-04-12012 April 2002 LER 02-02-00, Donald C. Cook Nuclear Plant Unit 2, Technical Specification 3.9.4.c Was Violated During Core Alteration ML0209205342002-03-15015 March 2002 LER 99-012-01 for Cook Nuclear Plant, Unit 1 Re Auxiliary Building ESF Ventilation System May Not Be Capable of Maintaining ESF Room Temperature Post-Accident ML9936300511999-12-20020 December 1999 LER 99-S004-00, Intentionally Falsifying Documentation Results in Unauthorized Unescorted Access, on 11/18/99. with Letter Dated 12/20/99 05000315/LER-1999-027, LER 315/99-027-00, Underrated Fuses Used in 250 Vdc System Could Result in Lack of Protective Coordination1999-11-29029 November 1999 LER 315/99-027-00, Underrated Fuses Used in 250 Vdc System Could Result in Lack of Protective Coordination ML18219E1521978-09-27027 September 1978 Submit Licensee Event Report Nos. RO 78-051/03L-0 & RO 78-052/03L-0 ML18219B5201978-09-27027 September 1978 09/27/1978 Letter Enclosure of Licensee Event Report ML18219B5211978-09-19019 September 1978 09/19/1978 Letter Enclosure of Licensee Event Report ML18219E1531978-09-18018 September 1978 Submit Licensee Event Report No. RO 78-050/03L-0 ML18219B5541978-09-18018 September 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 78-062/03L-0) ML18219B5551978-09-12012 September 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Reports (RO 78-56/03L-1 and RO 78-061/03L-0) ML18219E1541978-09-12012 September 1978 Submit Licensee Event Report No. RO 78-049/03L-0 ML18219E1551978-09-0808 September 1978 Submit Licensee Event Report No. RO 78-048/03L-0 ML18219B5561978-09-0808 September 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Reports (RO 78-059/03L-1 and RO 78-060/03L-0) ML18219B5571978-09-0505 September 1978 Letter from Indiana & Michigan Power Co to NRC Submitting License Event Report RO 78-059/03L-0 ML18219B5581978-08-30030 August 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report RO 78-058/03L-0 ML18219B5621978-08-22022 August 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Reports (RO 78-056/03L-0 and RO 78-057/03L-0) ML18219B5611978-08-18018 August 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Reports (RO 78-052/03L-0, RO 78-053/03L-0, RO 78-054-03L-0 and RO 78-055/03L-0) ML18219E1561978-08-15015 August 1978 Submit Licensee Event Report No. RO 78-047/03L-0 ML18219E1581978-08-14014 August 1978 Submit Licensee Event Report Nos. RO 78-043/03L-1 & RO 78-044/03L-1 ML18219E1571978-08-14014 August 1978 Submit Licensee Event Report Nos. RO 78-045/03L-0 & RO 78-046/03L-0 ML18219E1601978-08-11011 August 1978 Submit Licensee Event Report Nos. 1978-043-03L & 1978-044-03L ML18219B5641978-08-10010 August 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 78-051/03L-0) ML18219B5651978-08-0909 August 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 78-049/03L-1) ML18219B5661978-08-0808 August 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 78-050/03L-0) ML18219B5671978-08-0404 August 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 78-049/03L-0) ML18219B5681978-08-0202 August 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Reports (RO 78-029/03L-1 and RO 78-048/03L-0) ML18219B5691978-07-21021 July 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Reports (RO 78-019/03L-1 and RO 78-023/03L-1) ML18219B5701978-07-18018 July 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 78-047/03L-0) ML18219B5711978-07-11011 July 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 78-043/03L-0), Submitted Late Due to a Paper Defect ML18219B5721978-07-11011 July 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Reports (RO 78-034/03L-1, RO 78-044/03L-0, RO 78-045/03L-0, RO 78-046/03L-0) ML18219B5731978-07-0505 July 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 78-042/03L-0) ML18219B5751978-06-29029 June 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 50-316/78-037), Stating Corrective Actions Taken IR 05000316/19780371978-06-29029 June 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 50-316/78-037), Stating Corrective Actions Taken ML18219B5771978-06-22022 June 1978 D.C. Cook - Submit Licensee Event Report RO 78-036/03L-0 for Unit 2 ML18219B5761978-06-21021 June 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 78-035/03L-0), a Resubmittal of LER 78-034/03L-0 Dated 6/19/1978 ML18219B5781978-06-19019 June 1978 D.C. Cook - Submit Licensee Event Report RO 50-316/78-034/03L-0 for Unit 2 IR 05000316/19780341978-06-19019 June 1978 D.C. Cook - Submit Licensee Event Report RO 50-316/78-034/03L-0 for Unit 2 ML18219B5221978-06-0606 June 1978 06/06/1978 Letter Licensee Event Report 2024-09-12
[Table view] |
Text
r7 ~wv/o$
INFORMAT'IQN DISTRIBUTION SYSTEM (RIDS) 'EGULATORY DISTRIBUTION FOR INCQMING MATERIAL 50-316 REC: KEPPLER J G ORG: SHALLER D V DOCDATE: 05/05/78 NRC IN 5 MI PWR DATE RCVD: 05/ii/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED
SUBJECT:
LTR 1 ENCL 1 FORWARDING LICENSEE EVENT REPT (RO 50-316/78-022) ON 04/07/78 CONCERNING DURING NORMAL OPERATION ROD POSITION INDICATION FOR RODS D-12 AND H-8 EXCEEDED THE PLUS-MINUS 12 STEP LIMIT OF TECH SPEC 3. 1. 3. 2... W/ATT LER 78-023.
PLANT NAME: COOK UNIT 2 REVIEWER INITIAL: X JM DISTRIBUTOR INITIAL'PL@
DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS ++++<+<<++4<+<<<+<
NOTES:
SEND 3 COPIES OF ALL MATERIAL TO ISE INCIDENT REPORTS (DISTRIBUTION CODE A002)
FOR ACTION: BR CHIEF IEL4F~W/4 ENCL INTERNAL: EG FILE~~W/E C NRC PDR++W/ENCL MIPC4+W/3 ENCL SCl.lROEDER/IPPOLI TO4~+W/ENCL HOUSTON~~4W/ENCL NOVAK/CHECK+wW/ENCL EEB++W/ENCL KNIGHT4 +W/ENCL BUTLER4~W/ENCL HANAUER++W/ENCL TEDESCO++W/ENCL EI SENHUT+4 W/ENCL BAER~~W/ENCL SHAO>+W/ENCL VOLLMER/BUNCH>4W/ENCL KREGER/J. COLLINS+%W/ENCL ROSA44W/ENCI K SEYFRIT/IE+%W/ENCL FXTERNAL: LPDR S ST. JQSEPI-l. M I 4~W/ENCL T I C++W/ENCL NS IC4~+I l/ENCL ACRS CAT B+@W/16 ENCL COPIES NOT SUB.lITTED PERi REGULATORY GUIDE 10.1 DISTRIBUTION: LTR 45 ENCL 45 CONTROL NBR: 78 3200 6 SIZE: iP+1P+3P
,THE END
~4
~ \ L0 l4
IllOPIO4A INOIANA & MICHIOAAIPOWER COMPANY DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 May 5, 1978 Mr. J.G. Keppler, Regional Director Office of Inspection and Enforcement United States Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen El lyn, IL 60137 Operating License DPR-74 Docket No. 50-316
Dear Mr. Keppler:
Pursuant to the requirements of the Appendix A Technical Specifications the following reports are submitted:
RO 78-022/03L-0 RO 78-023/03L-O.
Sincerely, D.V. Shaller Plant Manager
/bab cc: J.ED Dolan "R.W. Jurgensen R.F. Kroeger R. Kilburn R.J. Vollen BPI K.RE Baker RO:III R.C. Callen MPSC P.W. Steketee, Esq.
R. Walsh, Esq.
G. Charnoff, Esq.
G. Olson J.M. Henni gan PNSRC J.F. Stietzel Dir., IE.(30 copies)
Dir., MIPC (3 copies)
~<
f tl
\ 1 P
)
NRC FORM 366 . S. NUCLEAR REGULATORY COMMISSION I7.77) 44 LiCENSEE EVENT REPORT CONTROL BLOCK: Qi IPLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)
I 6
~oi 7 8 9 M I D C LICENSEE CODE C 2 14 Q2 15 0 0 0 0 0 0 LICENSE NUMBER 0 0 0 0 UQ84 25 26 I 1 LICENSE TYPE 1 1QE~QE 30 57 CAT 58 CON'T
~oi """ ~LQR 0 5 0 0 0 3 1 6 QTO 4 0 7 7 8 Qs 0 5 0 5 7 8 Qs DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Qip DURING NORMAL OPERATION ROD POS ITON INDICATION ( RPI ) FOR RODS D 1 2 alld H 8 EXCEEDED THE + 1 2 STEP LIMIT OF T . S . 3. 1 .3.2. ON ELEVEN OTHER OCCASS IONS D-1 2 RPI WAS FOUND TO BE IN EXCESS OF THE T. S. LIMIT. IN ALL CASES THE ACTION REQUIRE-MENTS WERE FULFILLED. PREVIOUS OCCURRENCES OF A '-SIMILAR'NATURE INCLUDE:
o e RO 050/0315 78 07904 77 34933928927s76 54944s13 RO 050/0316 78 08>07
~ps 80 7 8 9 SYSTEM CAUSE CAUSE COMP. VALVE.
CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE
~IE Q>> E QT2 ~E Qls I N 5 7 R 0 Q14 ~I Qls ~Z'ls 7 8 9 10 11 12 13 18 19 20
~>> SEQUENTIAL OCCURRENCE REPORT REVISION LERIRO EVENT YEAR REPORT NO. CODE TYPE NO.
Qll REPoRT l77) 21 22 LJ 23 24 26 U>
27 LU~
28 29 "
Lil 30 LJ 31 L03 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRDQ PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METHOD HOURS Q22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER
~EQ18 33
~2 34 Qls ~2 35 Q20 ~Z 36 Q>>
37 0 0 0 0 40 41 Y Q22 ~Y 42 Q24 IJLI Q28 43 44 47 Q
CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27
~io THE SECONDARY VOLTAGE FOR D 1 2 AND H 8 WAS MEASURED AND FOUND TO BE CORRECT FOR THE ACTUAL DEMAND POSITION. THE OUTPUTS OF THE AMPLIFIERS THAT FEED THE CONTROL BOARD INDICATORS WERE FOUND TO BE INCORRECT. THE AMPLIFIERS WERE CALIBRATED AND PROPER OF HAVING A RECORDER CONNECTED TO THE ( SEE ATTACHED SUPPLEMENT) 7 8 9 80
~l>
FACILITY STATUS
~E Q28 ~03 56POWER 0 Q>>
OTHER STATUS NA
~
~3P METHOD OF DISCOVERY
~Q>>
DISCOVERY DESCRIPTION Q32 8 9 10 12 13 44 45 46 80 6
ACTIVITY CONTENT RELEASED OF RELEASE
~Z Q33 Z Q34 AMOUNTOF ACTIVITY NA
~ LOCATION OF RELEASE QB 7 8 9 10 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39
~l7 ~00 0 Q>>L~ JQER NA 80 7 8 9 11 12 13 PERSONNEL INJURIES NUMBER OESCRIPTIONQ41
~18 ~OO O Qs NA 7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION Q43 Z NA 7 8 9 10 80 PUBLICITY DESCRIPTION Q NRC USE ONLY O ZZ 7 8 ISSUED WZQ44 9 10 NA 68 69 80 o 44 a
9 Jack Rjschling 6-.465-5 0 a
NAME OF PREPARER PHDNE: ~ ~ 47
o
';lhI;)Il)T'. P I
LICENSEE EVENT REPORT 878-022/03L-0 SUPPLEMENT TO CAUSE DESCRIPTI'ON OUTPUT OF THE RPI CABINET(NONI'TORING D-12;) THI'S RECORDER WAS CONNECTED IN PREPARATION FOR THE NEGATIVE RATE TRIP ASSOCl'ATED Ml'TH THE POWER ASCENSION PROGRPI, SI'NCE THl'S RECORDER WAS Dl'SCONNECTED ON APRIL 19,1978 NO FURTHER PROBLEMS HAVE BEEN ENCOUNTERED WITH RPI fOR ROD D-12.
(
/
NRC FORM 366 I7.77) n ~ ',
CONTROL BLOCK:
I LICENSEE EVENT REPORT 6
Q1 1.
U. S. NUCLEAR REGULATORY COMMISSION (PLEASE PRINT OR TYPE ALI REQUIRED INFORMATION)
[os]
7 8 9 14 I D LICENSEE CODE C C 2Q20 14 15 0 0 0 0 0 LICENSE NUMBER 0 0 0 0 0 25 Q34 26 1 1 I LICENSE TYPE I
30 QR~QE 57 CAT 58 CON'T
~RT "" ~LQE 0 5 0 0 0 3 1 6 QT 0 4 0 8 7 8 QE 0 6 0 6 Q 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10
~o2 DURING STARTUP AND POWER ASCENSION PROGRAM THE STEAN PRESSURE BISTABLES PB-516A,526A,536A and 546A (LOW PRESSURE-STEAM LINE ISOLATION) WERE NOT 4 FUNCTIONALLY TESTED PER T. S. TABLE 4.3-2 Imt4.e.
~OS
~O6
~O7
~OS 80 7 8 9 SYSTEM CAUSE CAUSE COMP. VALVE, CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE
~BQTT A Q12 ~CQ>> I ll S T R U QR ~QR ~z 20 Q'8 7 8 9 10 11 12 13 18 19 SEQUENTIAL OCCURRENCE REPORT REVISION LF RIP EVENT YEAR REPORT NO. CODE TYPE NO.
Q11 REPoRT ~78 21 22 Q
23
~02 24 3
26 Q~
27
~03 28 29 QL 30
[J 31 QO 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRD 4 PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METHOD HOURS O22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER
~GQEE~ZQTR ~ZQEE ~ZQET O O O 91 I Q23 ~NQ24 ~NQEE W I 2 O QER 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 p A DESIGN CHANGE WAS COMPLETED REMOVING THESE BISTABLES FROM PROTECTION SETS I II AND IV, AND INSTALLING THEM IN SETS'I AND II. TEMPORARY CHANGES WERE WRITTEN ADDING THESE BISTABLES TO THE APPROPIATE PROCEDURES. THESE TEMPORARY CHANGE SHEETS WERE MISPLACED AND NOT PLACED INTO EFFECT. CONSEQUENTLY, THE BISTABLES WERE NOT FUNCTION-4 ALLY TESTED IN FEBRUARY AND MARCH. ( SEE ATTACHED SUPPLEMENT) 7 .8 9
~18 FACILITY STATUS
~B Q28 ~04 SGPOWER 0 Q28 OTHERSTATUS NA
~
~3P -
METHOD OF DISCOVERY
~AQ31 ROUTINE REVIEW DISCOVERY DESCRIPTION Q32 7 8 9 10 12 13 44 45 46 80 I
ACTIVITY CONTENT RELEASED OF RELEASE LzlO uz8 AMOUNT OF ACTIVITY NA
~ LOCATION OF RELEASE Q 7 8 9 10 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39 1
8
~00 0 QRT Z Q38 13 NA 80 7 9 11 12 PERSONNCL INJURIES NUMBER DESCRIPTIONQ41 7
8 8
~00 9
0 QR 11 12 NA 80 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION Q43 z Q42 NA 7 8 9 10 80
~2o ISSUED P U8 L LZ l04" I CITY DESCRIPTION ~ NRC USE ONLY 8 9 10 68 69 80 o 0
NAME OF PREPARER Jack Rischlin PHDNE, 61 6 465 5901
'1 I
ATTACHMENT TO LICENSEE EVENT REPORT 8 78-023/03L-0 Cause Description THESE HAVE BEEN ADDED TO THE APPROPIATE PROCEDURES AND FUNCTIONALLY TESTED.